JPS6332399A - Processing vessel for radioactive waste, etc. and manufacture thereof - Google Patents
Processing vessel for radioactive waste, etc. and manufacture thereofInfo
- Publication number
- JPS6332399A JPS6332399A JP61175410A JP17541086A JPS6332399A JP S6332399 A JPS6332399 A JP S6332399A JP 61175410 A JP61175410 A JP 61175410A JP 17541086 A JP17541086 A JP 17541086A JP S6332399 A JPS6332399 A JP S6332399A
- Authority
- JP
- Japan
- Prior art keywords
- concrete
- container
- water
- formwork
- curing
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Pending
Links
- 239000002901 radioactive waste Substances 0.000 title claims description 11
- 238000004519 manufacturing process Methods 0.000 title claims description 10
- 239000004567 concrete Substances 0.000 claims description 42
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 34
- 239000004568 cement Substances 0.000 claims description 12
- 238000005056 compaction Methods 0.000 claims description 12
- 238000000034 method Methods 0.000 claims description 12
- 238000009415 formwork Methods 0.000 claims description 11
- 239000012779 reinforcing material Substances 0.000 claims description 7
- 229910021487 silica fume Inorganic materials 0.000 claims description 7
- 239000003638 chemical reducing agent Substances 0.000 claims description 5
- 229910052751 metal Inorganic materials 0.000 claims description 5
- 239000002184 metal Substances 0.000 claims description 5
- 239000002994 raw material Substances 0.000 claims description 3
- 239000000203 mixture Substances 0.000 claims description 2
- 239000012615 aggregate Substances 0.000 claims 2
- 239000011372 high-strength concrete Substances 0.000 claims 1
- 229910000831 Steel Inorganic materials 0.000 description 10
- 239000010959 steel Substances 0.000 description 10
- VYPSYNLAJGMNEJ-UHFFFAOYSA-N Silicium dioxide Chemical compound O=[Si]=O VYPSYNLAJGMNEJ-UHFFFAOYSA-N 0.000 description 9
- 239000010802 sludge Substances 0.000 description 7
- 238000002156 mixing Methods 0.000 description 6
- 230000007797 corrosion Effects 0.000 description 5
- 238000005260 corrosion Methods 0.000 description 5
- 230000000694 effects Effects 0.000 description 5
- RYGMFSIKBFXOCR-UHFFFAOYSA-N Copper Chemical compound [Cu] RYGMFSIKBFXOCR-UHFFFAOYSA-N 0.000 description 4
- 229910052802 copper Inorganic materials 0.000 description 4
- 239000010949 copper Substances 0.000 description 4
- 229910001385 heavy metal Inorganic materials 0.000 description 4
- 239000002925 low-level radioactive waste Substances 0.000 description 4
- 239000000377 silicon dioxide Substances 0.000 description 4
- 230000008020 evaporation Effects 0.000 description 3
- 238000001704 evaporation Methods 0.000 description 3
- 239000000835 fiber Substances 0.000 description 3
- 239000002245 particle Substances 0.000 description 3
- 230000003014 reinforcing effect Effects 0.000 description 3
- 230000035939 shock Effects 0.000 description 3
- 239000000853 adhesive Substances 0.000 description 2
- 230000001070 adhesive effect Effects 0.000 description 2
- 239000010426 asphalt Substances 0.000 description 2
- 230000009970 fire resistant effect Effects 0.000 description 2
- 239000003365 glass fiber Substances 0.000 description 2
- 239000000383 hazardous chemical Substances 0.000 description 2
- 230000005855 radiation Effects 0.000 description 2
- 239000000941 radioactive substance Substances 0.000 description 2
- 239000011347 resin Substances 0.000 description 2
- 229920005989 resin Polymers 0.000 description 2
- 239000013535 sea water Substances 0.000 description 2
- 239000000126 substance Substances 0.000 description 2
- GUTLYIVDDKVIGB-OUBTZVSYSA-N Cobalt-60 Chemical compound [60Co] GUTLYIVDDKVIGB-OUBTZVSYSA-N 0.000 description 1
- 239000004593 Epoxy Substances 0.000 description 1
- UFWIBTONFRDIAS-UHFFFAOYSA-N Naphthalene Chemical compound C1=CC=CC2=CC=CC=C21 UFWIBTONFRDIAS-UHFFFAOYSA-N 0.000 description 1
- 238000005452 bending Methods 0.000 description 1
- AXCZMVOFGPJBDE-UHFFFAOYSA-L calcium dihydroxide Chemical compound [OH-].[OH-].[Ca+2] AXCZMVOFGPJBDE-UHFFFAOYSA-L 0.000 description 1
- 239000000920 calcium hydroxide Substances 0.000 description 1
- 229910001861 calcium hydroxide Inorganic materials 0.000 description 1
- OYACROKNLOSFPA-UHFFFAOYSA-N calcium;dioxido(oxo)silane Chemical class [Ca+2].[O-][Si]([O-])=O OYACROKNLOSFPA-UHFFFAOYSA-N 0.000 description 1
- 239000011248 coating agent Substances 0.000 description 1
- 238000000576 coating method Methods 0.000 description 1
- 230000007547 defect Effects 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 239000010419 fine particle Substances 0.000 description 1
- 230000036571 hydration Effects 0.000 description 1
- 238000006703 hydration reaction Methods 0.000 description 1
- 238000004898 kneading Methods 0.000 description 1
- 230000007774 longterm Effects 0.000 description 1
- 239000000155 melt Substances 0.000 description 1
- 239000006082 mold release agent Substances 0.000 description 1
- 238000000465 moulding Methods 0.000 description 1
- 239000012857 radioactive material Substances 0.000 description 1
- 150000003839 salts Chemical class 0.000 description 1
- 239000004576 sand Substances 0.000 description 1
- 238000007789 sealing Methods 0.000 description 1
- 239000002352 surface water Substances 0.000 description 1
- 239000002699 waste material Substances 0.000 description 1
Landscapes
- Processing Of Solid Wastes (AREA)
Abstract
(57)【要約】本公報は電子出願前の出願データであるた
め要約のデータは記録されません。(57) [Abstract] This bulletin contains application data before electronic filing, so abstract data is not recorded.
Description
【発明の詳細な説明】
（産業上の利用分野）
本発明は、放射性廃棄物及び重金属スラッジ等の有害物
質の処理処分容器及びその製造方法に関するものである
。DETAILED DESCRIPTION OF THE INVENTION (Field of Industrial Application) The present invention relates to a container for processing and disposing of hazardous substances such as radioactive waste and heavy metal sludge, and a method for manufacturing the same.
更に詳細には、本発明は、原子力発電所や原子力研究所
などの原子力事業所や、医療関係で用いられる放射線源
で発生する中、低レベル放射性廃棄物並びに化学工場等
で発生するを害物を含む汚泥、メソキ工場から発生する
メンキスラッジ、重金属スラッジ等の処理処分容器及び
その製造方法に関するものである。More specifically, the present invention deals with the treatment of harmful substances such as low-level radioactive waste generated at nuclear power plants, nuclear power research institutes, and other nuclear power plants, radiation sources used in the medical field, and chemical factories. The present invention relates to a container for treating and disposing of sludge containing sludge, menkis sludge generated from the Mesoki factory, heavy metal sludge, etc., and a method for manufacturing the same.
（従来の技術）
従来、原子力発電所で発生する中、低レベル放射性廃棄
物は、鋼製ドラム缶ないし鋼製ドラム缶を外殻として樹
脂を含浸させたコンクリートを内殻とする容器に収納し
、セメント或いはアスファルト等で固化する方法や、ド
ラム缶をそのまま用いて、セメント或いはアスファルト
等で固化する方法、及び単なるコンクリート製容器に同
様に固化する方法等が発表されている。(Prior technology) Conventionally, low-level radioactive waste generated at nuclear power plants is stored in steel drums or containers with an outer shell of steel drums and an inner shell of concrete impregnated with resin. Alternatively, a method of solidifying with asphalt, etc., a method of using a drum as it is and solidifying with cement or asphalt, etc., and a method of similarly solidifying into a simple concrete container have been announced.
これら中、低レベル放射性廃棄物や重金属スラッジ等の
処理用容器に鋼製ドラム缶が用いられている理由は、大
きさや価格が手頃で市場に出回ってそいるため入手し易
く、各種の荷投機械があることにより、取扱が比較的容
易であることによる。Among these, steel drums are used as containers for processing low-level radioactive waste and heavy metal sludge, etc. The reason why steel drums are used is that they are easy to obtain due to their reasonable size and price, and are widely available on the market. This is because it is relatively easy to handle.
周知のように、放射性廃棄物はコバルト６０などの放射
性物質を含んでおり、ある以上のレベルの放射能は人体
や周辺環境に有害であるし、放射性物質はそれぞれの核
種によって半減期が異なり、人体や周辺環境に安全上支
承のない放射能レベルまで減衰するまでの期間、安全に
隔離、保管する必要がある。As is well known, radioactive waste contains radioactive substances such as cobalt-60, and radioactivity above a certain level is harmful to the human body and the surrounding environment, and each radioactive substance has a different half-life depending on its nuclide. It must be safely isolated and stored until the radioactivity has decayed to a level that is safe for humans and the surrounding environment.
そのためには、安全上支障のないレベルまで減衰するに
要する期間はおおよそ１００年程度と言われている。従
って中、低レベル放射性廃棄物を安全に隔離、保管する
には１００年程度の耐久性を有する容器が必要である。To achieve this, it is said that it will take approximately 100 years for the energy to decay to a level that does not pose a safety problem. Therefore, to safely isolate and store medium- to low-level radioactive waste, containers with durability of about 100 years are required.
（発明が解決しようとする問題点）
しかし、現在用いられている鋼製ドラム缶は、鋼十反の
厚さが１ 、２ｍｍ〜１６ｍｍと薄く腐食によって１０
０年の長期間の耐久性は全くなく、また深海への投棄、
いわゆる海洋処分を行うとすれば、海水の塩分による腐
食は大きく、銅製ドラム缶容器は全（不向きである。又
処理処分容器には、輸送中や取扱い時の衝撃に対する耐
衝撃性、保管中の火災等に対する耐火性、深海の水圧に
対する耐高水圧性、放射性物質の漏洩防止のための不透
水性が必要である。(Problems to be Solved by the Invention) However, the steel drums currently in use have a thickness of 1.2 mm to 16 mm, and are easily damaged by corrosion.
It has no long-term durability of 0 years, and it can be dumped into the deep sea.
If so-called ocean disposal is to be carried out, corrosion due to salt in the seawater is severe, and copper drum containers are completely unsuitable.Also, treatment and disposal containers must be shock resistant to shocks during transportation and handling, and fire resistant during storage. It is necessary to have fire resistance against water pressure, etc., high water pressure resistance against deep sea water pressure, and impermeability to prevent leakage of radioactive materials.
従って、従来の鋼製ドラム缶の内面にコンクリートを打
設し、コンクリートに樹脂を含浸させた容器や、通常の
セメントに補強材を添加した特開昭５９−８５９９９号
公報発明の如きコンクリート容器では、前者にあっては
高温になると溶融して強度が低下し、耐火性、耐熱性に
乏しい欠点がある。Therefore, in conventional containers made of steel drums with concrete poured on the inner surface and impregnated with resin, and in concrete containers such as the invention of JP-A-59-85999, in which a reinforcing material is added to ordinary cement, The former has the disadvantage that it melts at high temperatures, reduces strength, and has poor fire resistance and heat resistance.
また、後者にあっては、深海の高水圧（６００ｋｇ・ｆ
／ｃｍ２程度）に耐える高強度と曲げ、及び引張応力、
耐衝撃性が充分得られないことと、漏洩防止のための不
透水性に乏しい欠点を有している。In addition, in the latter case, high water pressure in the deep sea (600 kg・f
/cm2) high strength, bending and tensile stress,
It has the drawbacks of insufficient impact resistance and poor water impermeability to prevent leakage.
（問題点を解決するための手段）
本発明は上記のような事情に鑑みてなされたもので、シ
リカヒユーム及び補強材を含有する張緻密なコンクリー
トより構成された不透水性、耐火性、耐衝撃性及び１０
００ｋｇ・ｆ／ｃｍ”以上を持つ超高強度コンクリート
製容器ないし該コンクリート製容器が金属製容器からな
る外殻と一体となす放射性廃棄物等の処理処分容器及び
その製造方法にある。これによって本発明は、耐腐食性
、耐火性及び耐高水圧に優れた放射性廃棄物等の処理処
分容器を提供せんとするものである。(Means for Solving the Problems) The present invention has been made in view of the above-mentioned circumstances, and consists of a water-impermeable, fire-resistant, and shock-resistant concrete structure made of dense concrete containing silica hume and reinforcing material. sex and 10
00 kg・f/cm" or more, or a container for processing and disposing of radioactive waste, etc., in which the concrete container is integrated with an outer shell made of a metal container, and a method for manufacturing the same. The present invention aims to provide a container for processing and disposing of radioactive waste, etc., which has excellent corrosion resistance, fire resistance, and high water pressure resistance.
以下本発明について説明すると、本発明の最大の特徴は
、セメントにシリカヒユーム（以下ＳＦと言う）を添加
することにある。The present invention will be described below. The greatest feature of the present invention is that silica fume (hereinafter referred to as SF) is added to cement.
このＳＦを普通のセメントコンクリートに添加すると、
セメントの水和によって生ずる水酸化カルシウムとポヅ
ラン活性の高いＳＦが反応し、セメントのみで生成する
場合以外のカルシウムシリケート化合物を生成すること
＼、セメント粒子間に粒子径の小さいＳＦが入り込み、
微粒子の充填効果が生ずることによって、緻密で強固な
組織となる。よって極めて高い強度と不透水性が得られ
る。すなわち、樹脂含浸コンクリートとは比較にならな
い程高＜ 、１０００ｋｇ・ｆ／ｃｍ２以上の高強度が
得られるものである。更に補強材として、ガラス繊維１
銅繊維１鉄筋等を混入することによって耐衝撃性の向上
と、耐高木圧の補強に役立つものである。When this SF is added to ordinary cement concrete,
Calcium hydroxide produced by hydration of cement reacts with SF with high podulan activity, producing calcium silicate compounds other than those produced by cement alone. SF with small particle size enters between cement particles,
The filling effect of the fine particles creates a dense and strong structure. This results in extremely high strength and water impermeability. That is, it is possible to obtain a high strength of 1000 kg·f/cm2 or more, which is incomparably higher than that of resin-impregnated concrete. Furthermore, as a reinforcing material, glass fiber 1
By mixing copper fiber 1 reinforcing bars, etc., it is useful for improving impact resistance and reinforcing high tree pressure resistance.
このＳＦを添加したコンクリート（以下ＳＦコンクリー
トと言う）からなる容器、ないしこのＳＦコンクリート
製容器を、金属製容器である耐蝕性保護のための防蝕被
覆した銅製ドラム缶などからなる外殻と一体に構成され
た放射性廃棄物等の処理処分容器をなすものである。A container made of concrete to which SF has been added (hereinafter referred to as SF concrete), or a container made of SF concrete, is integrally constructed with an outer shell made of a metal container such as a copper drum coated with a corrosion-resistant coating for corrosion-resistant protection. It serves as a treatment and disposal container for radioactive waste, etc.
次に、その製造方法を第１図に示す工程図に基づいて説
明する。Next, the manufacturing method will be explained based on the process chart shown in FIG.
先ず型枠を清掃し、離型剤を塗布した後組立てるのであ
るが、外殻にドラム缶を用いた容器を製造する場合には
、ドラム缶内に内型枠を設置した後組立てる。First, the formwork is cleaned and a mold release agent is applied before assembly. However, when manufacturing a container using a drum for the outer shell, the inner formwork is installed inside the drum and then assembled.
次に、セメント、シリカヒユーム、骨材、補強材を予め
計量し、特に骨材にあっては表面水を測定し水量を補正
した後、ミキサーに投入し空練りを行う。Next, the cement, silica hum, aggregate, and reinforcing material are weighed in advance, and in particular, the surface water of the aggregate is measured and the amount of water is corrected, and then the mixture is put into a mixer and subjected to dry kneading.
引続き、水及び減水剤をミキサーに投入し本線りを行う
。この場合に、ＳＦコンクリートは不遇水性、高強度、
耐火性が得られる反面、粘性が高く、ワーカビリティの
低下と、超緻密、高強度を得るための原材料の品質、管
理、混練や養生等の製造技術の面で従来のセメントコン
クリートとは異った方法が必要とされる。Next, add water and water reducing agent to the mixer and perform the main mixing. In this case, SF concrete is water-resistant, has high strength,
Although it has fire resistance, it is different from conventional cement concrete in terms of high viscosity and reduced workability, and manufacturing techniques such as quality of raw materials, management, mixing and curing to obtain ultra-dense and high strength. A new method is needed.
その第１は、硬化に必要な水の量以上は加えないこと、
すなわち、硬化に必要な水の量を加えるのみで、過剰な
余剰水を与えることは好ましくない。このため、減水剤
を添加することにより水の量を最小にして高強度と良好
なワーカビリチーを得ようとするものである。First, do not add more water than is necessary for curing.
That is, it is not preferable to add an excessive amount of surplus water only by adding the amount of water necessary for curing. Therefore, by adding a water reducing agent, the amount of water is minimized to obtain high strength and good workability.
本線りが完了すると、次は型枠にＳＦコンクリートを打
設する。コンクリートの混練、打設時に混入する空気は
、締固めを十分に行わないと気泡としてコンクリート中
に残る。前述のようにＳＦコンクリートは水量を抑える
こともあって、粘性が高く、気泡が抜けにくい。そこで
振動締固め及び遠心締固めを行うことにより気泡を抜く
方法が採られている。Once the main line is completed, the next step is to pour SF concrete into the formwork. Air that gets mixed into the concrete during mixing and pouring will remain in the concrete as air bubbles if the concrete is not sufficiently compacted. As mentioned above, SF concrete has a high viscosity, which makes it difficult for air bubbles to escape, partly because the amount of water is suppressed. Therefore, methods have been adopted to remove air bubbles by performing vibration compaction and centrifugal compaction.
一般に振動締固めでは、振動周波数が高くなるにつれて
気泡は抜は易（なり、ある周波数以上では逆に抜けにく
くなる。ＳＦコンクリートの振動締固めでは、ａｏｏｏ
〜９ＱＯＯＨ２付近で最も気泡の抜けが良くて強度も大
きい。これに対し、６０００Ｈｚ以下及び１００００Ｈ
ｚ以上の周波数では気泡も抜けにくく強度も小さい。従
って、ＳＦコンクリートの振動締固めでは、約６，００
０〜１０．０ＯＯＨｚの範囲内での振動周波数を用いる
と気泡の抜けが良く又、粒径の微細化がなされる。又遠
心力を利用した遠心締固めを行う場合には、約１００以
上の遠心力を与えると効果がある。In general, in vibration compaction, air bubbles are easier to remove as the vibration frequency increases, and on the contrary, it becomes difficult to remove air bubbles above a certain frequency.
The air bubbles are removed best around ~9QOOH2 and the strength is also high. On the other hand, below 6000Hz and 10000H
At frequencies above z, bubbles are difficult to escape and the strength is low. Therefore, in vibration compaction of SF concrete, approximately 6,000
If a vibration frequency within the range of 0 to 10.000Hz is used, air bubbles can be removed easily and the particle size can be made finer. Furthermore, when performing centrifugal compaction using centrifugal force, it is effective to apply a centrifugal force of about 100 or more.
このように、シリカヒユームの添加、過剰な余剰水を出
来る限り与えないで蒸発による水分の喪失を防ぎ、気泡
の除去に有効な振動周波数帯にて振動締固めを行う、又
は遠心力を利用して遠心締固めを行い、超緻密なＳＦコ
ンクリートを得ることができる。すなわち、緻密なコン
クリートを得るためには、内部空隙の少ないコンクリー
トを得ることであり、言い換えれば、気泡の少ないコン
クリートを得ることである。In this way, it is possible to add silica hume, prevent water loss by evaporation by adding as little excess water as possible, perform vibration compaction in a vibration frequency band that is effective for removing air bubbles, or use centrifugal force. Ultra-dense SF concrete can be obtained by centrifugal compaction. That is, in order to obtain dense concrete, it is necessary to obtain concrete with few internal voids, or in other words, to obtain concrete with few air bubbles.
コンクリート中の気泡は、余剰水の蒸発によって生ずる
もの、或いは振動、遠心力による締固めが不十分である
ために、混錬時及び打設時に混入して生ずる。気泡の存
在する部位は、いわゆる断面欠損となり強度が低下する
のである。したがって、硬化に必要のない余剰水を出来
るだけ与えないよう、Ｗ／Ｃを１５〜３５％に抑えるこ
とにより、余剰水の蒸発による気泡の発生を防ぐことが
必要である。Bubbles in concrete are caused by the evaporation of excess water, or are caused by insufficient compaction due to vibration or centrifugal force, which causes them to be mixed in during mixing and pouring. Areas where air bubbles exist become so-called cross-sectional defects, resulting in a decrease in strength. Therefore, it is necessary to prevent the generation of bubbles due to evaporation of excess water by suppressing the W/C to 15 to 35% so as to avoid adding excess water that is not necessary for curing as much as possible.
締固めた後、打設面をコテ等により仕上げを行い、表面
を平滑にした後蒸気養生を行ない、養生後説型する。ま
た脱型後に水中養生、温水養生。After compaction, the pouring surface is finished with a trowel, etc., the surface is made smooth, steam curing is performed, and after curing, a final mold is made. Also, after demolding, water curing and hot water curing.
高温高圧蒸気養生等を行っても良い。High-temperature, high-pressure steam curing, etc. may also be performed.
第２図、第３図は得られた製品の（イ）は全体斜視図、
（ロ）はその断面図であり、第２図中１は製品本体、２
はＳＦコンクリートの蓋、３は本体１と蓋２とをエポキ
シ等接着剤で溶着された部分を示す。又第３図中４は鋼
製ドラム缶で、該鋼製ドラム缶４を外殻とした容器の内
側に、ＳＦコンクリート本体１を収納し、一体に構成し
た容器である。第４図は、更に別の実施例であり、図中
５は鉄筋で、Ｍ２の部分をＳＦコンクリートで後打ちし
たものである。Figures 2 and 3 show the obtained product; (A) is an overall perspective view;
(B) is its cross-sectional view, and in Fig. 2, 1 is the product body, 2
3 shows the SF concrete lid, and 3 shows the part where the main body 1 and the lid 2 are welded together with an adhesive such as epoxy. Further, 4 in FIG. 3 is a steel drum, and the SF concrete main body 1 is housed inside the container with the steel drum 4 as an outer shell, and is an integrally constructed container. FIG. 4 shows yet another embodiment, in which 5 is a reinforcing bar, and the M2 portion is post-cast with SF concrete.
（実施例）
セメント ・・・・・・・ ４００ｋｇシリカヒユ
ーム・・・・・ ８０に＋ｒ骨材（砂、砂利）・・
・・ １７９４ｋｇ鋼繊維 ・・・・・・・・
１５６ｋｇ水 ・ ・ ・ ・ ・ ・ ・ ・ ・
１１０ｋｇ減水剤（マイティー１５０）・
１２ｋｇを配し、ミキサーにより混練し、これを外型
枠と内型枠中に流し込んだ後、振動成型を行い、２時間
放置後６０℃３時間蒸気養生を施した。(Example) Cement...400kg silica hume...80+r aggregate (sand, gravel)...
・・・ 1794kg steel fiber ・・・・・・・・・
156kg water ・ ・ ・ ・ ・ ・ ・ ・ ・
110kg water reducing agent (Mighty 150)・
After 12 kg was placed and kneaded using a mixer, this was poured into the outer mold and the inner mold, vibration molding was performed, and after being left for 2 hours, steam curing was performed at 60° C. for 3 hours.
その後脱型して円筒型ＳＦコンクリートを取出した。コ
ンクリートの平均肉厚３０ｍｍであった。After that, the mold was removed and the cylindrical SF concrete was taken out. The average wall thickness of the concrete was 30 mm.
この供試体についての外圧試験を行った結果、 ４゜１
２００ｋｇ−ｆ／ｃｍ”であり、また１、５ｍからの水
平落下試験を行った。その結果は、水漏れや、破壊、落
下衝撃によるクランクの発生や蓋のシール用部分のはず
れは全く生じなかった。As a result of an external pressure test on this specimen, 4゜1
200kg-f/cm'', and a horizontal drop test from 1.5m was conducted.The results showed that there was no water leakage, no breakage, no cranking due to drop impact, and no detachment of the sealing part of the lid. Ta.
（作用・効果）
以上詳述したように、放射性廃棄物及び重金属スラッジ
等存害物質を含む廃棄物の処理処分容器として、コンク
リートの性能を生かし放射線の遮蔽効果は高く、又シリ
カヒユームを添加することによって極めて緻密な構造か
ら不透水性、耐火性に極めて優れ、更にはガラス繊維、
銅繊維等の混入によって耐衝撃性の向上を図り、且つＳ
Ｆコンクリートの持つ高強度、耐高水圧が顕著に高く、
外殻にドラム缶を用いる場合には、ドラム缶用の荷投機
械が使用出来、既存の処理設備を利用する顕著な効果が
得られるものである。(Function/Effect) As detailed above, as a treatment and disposal container for waste containing hazardous substances such as radioactive waste and heavy metal sludge, concrete has a high radiation shielding effect by taking advantage of its performance, and the addition of silica fume. Due to its extremely dense structure, it has excellent water impermeability and fire resistance, and is also made of glass fiber,
The impact resistance is improved by mixing copper fiber etc., and S
F concrete has significantly high strength and high water pressure resistance,
When a drum can is used for the outer shell, a loading machine for drum cans can be used, and a remarkable effect can be obtained by using existing processing equipment.
よって安全性の高い放射性廃棄物の収納が可能となるな
ど、その実用性と有用性は極めて高いものである。Therefore, its practicality and usefulness are extremely high, as it allows highly safe storage of radioactive waste.
第１図は本発明の製造工程図、第２図及び第３図は本発
明により得られた製品を示し、（イ）は全体斜視図、
（ロ）はその縦断面図、第４図は他の実施例の製品の縦
断面図である。
１・・本体、 ２・・ＳＦコンクリート蓋、３・・接
着部、 ４・・鋼製ドラム缶からなる外殻、 ５・・鉄
筋。FIG. 1 is a manufacturing process diagram of the present invention, FIGS. 2 and 3 show products obtained by the present invention, and (A) is an overall perspective view;
(B) is a longitudinal sectional view thereof, and FIG. 4 is a longitudinal sectional view of a product of another embodiment. 1. Main body, 2. SF concrete lid, 3. Adhesive part, 4. Outer shell made of steel drum, 5. Rebar.
Claims (3)
ンクリートより構成した不透水性、耐火性、耐衝撃性並
びに１０００ｋｇ・ｆ／ｃｍ＾２以上を持つ超高強度コ
ンクリート製容器ないし該コンクリート製容器が金属製
容器からなる外殻と一体となすことを特徴とする放射性
廃棄物等の処理処分容器。(1) A container made of ultra-high strength concrete that is made of ultra-dense concrete containing silica fume and reinforcing material and has water impermeability, fire resistance, impact resistance, and 1000 kg・f/cm^2 or more, or the concrete container. 1. A container for processing and disposing of radioactive waste, etc., which is integrated with an outer shell made of a metal container.
ら成る型枠に、主としてセメント、シリカヒューム、骨
材、水、減水剤および補強材から成る原材料を混練して
打設し、その後振動締固めを行った後に養生、脱型を行
い、又は脱型、養生の順で行って、シリカヒューム添加
による超緻密なコンクリートを構成した不透水性、耐火
性、耐衝撃性並びに超高強度を有するコンクリート製容
器ないし、外殻と一体に構成せしめたことを特徴とする
放射性廃棄物等の処理処分容器の製造方法。(2) Raw materials mainly consisting of cement, silica fume, aggregate, water, water reducer, and reinforcing material are mixed and poured into a formwork consisting of an outer shell made of an outer formwork or a metal container and an inner formwork. , followed by vibratory compaction followed by curing and demolding, or by demolding and curing in that order, resulting in ultra-dense concrete with silica fume addition, which has excellent water-impermeability, fire resistance, impact resistance, and A method for manufacturing a container for processing and disposing of radioactive waste, etc., characterized in that the container is made of concrete having high strength or is constructed integrally with an outer shell.
ら成る型枠に、主としてセメント、シリカヒューム、骨
材、水、減水剤および補強材から成る原材料を混練して
その底部に打設し、振動締固めを行った後に養生を行い
、引続き遠心締固め用型枠に設置して胴部に該コンクリ
ートを打設し、養生、脱型又は脱型、養生の順で行うか
、又は胴部を先に遠心成形し、その後底部の振動成形を
行ってなるシリカヒューム添加及び遠心締固めによる超
緻密なコンクリートを構成した不透水性、耐火性、耐衝
撃性並びに超高強度を有するコンクリート製容器ないし
外殻と一体に構成せしめたことを特徴とする放射性廃棄
物等の処理処分容器の製造方法。(3) Raw materials mainly consisting of cement, silica fume, aggregate, water, water reducer, and reinforcing material are mixed into a formwork consisting of an outer shell made of an outer formwork or a metal container and an inner formwork, and the mixture is poured into the bottom of the formwork. After pouring and vibrating compaction, curing is performed, and then the concrete is placed in a centrifugal compaction formwork and the concrete is poured into the body, followed by curing, demolding, or demolding, and curing in this order. Or, the body is first centrifugally formed, and then the bottom part is vibrated, and ultra-dense concrete is created by adding silica fume and centrifugally compacting to achieve water impermeability, fire resistance, impact resistance, and ultra-high strength. 1. A method for manufacturing a container for processing and disposing of radioactive waste, etc., characterized in that the container is integrally constructed with a concrete container or outer shell having a container made of concrete.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP61175410A JPS6332399A (en) | 1986-07-25 | 1986-07-25 | Processing vessel for radioactive waste, etc. and manufacture thereof |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP61175410A JPS6332399A (en) | 1986-07-25 | 1986-07-25 | Processing vessel for radioactive waste, etc. and manufacture thereof |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS6332399A true JPS6332399A (en) | 1988-02-12 |
Family
ID=15995606
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP61175410A Pending JPS6332399A (en) | 1986-07-25 | 1986-07-25 | Processing vessel for radioactive waste, etc. and manufacture thereof |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS6332399A (en) |
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH0319998U (en) * | 1989-07-05 | 1991-02-27 | ||
| JP2006518446A (en) * | 2003-01-13 | 2006-08-10 | フォルスター，ヤン | Building structure for buildings protected against radiation |
| JP2013142618A (en) * | 2012-01-11 | 2013-07-22 | Shimizu Corp | Volume reduction method and device for concrete contaminated with radiation |
| JP2013217658A (en) * | 2012-04-04 | 2013-10-24 | Fujita Corp | Radiation shielding concrete container and method for managing contaminated soil |
Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS61245095A (en) * | 1985-04-23 | 1986-10-31 | 電気化学工業株式会社 | Waste treating vessel |
-
1986
- 1986-07-25 JP JP61175410A patent/JPS6332399A/en active Pending
Patent Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS61245095A (en) * | 1985-04-23 | 1986-10-31 | 電気化学工業株式会社 | Waste treating vessel |
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH0319998U (en) * | 1989-07-05 | 1991-02-27 | ||
| JP2006518446A (en) * | 2003-01-13 | 2006-08-10 | フォルスター，ヤン | Building structure for buildings protected against radiation |
| JP2013142618A (en) * | 2012-01-11 | 2013-07-22 | Shimizu Corp | Volume reduction method and device for concrete contaminated with radiation |
| JP2013217658A (en) * | 2012-04-04 | 2013-10-24 | Fujita Corp | Radiation shielding concrete container and method for managing contaminated soil |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| US4687614A (en) | Process for producing a high integrity container | |
| US5545796A (en) | Article made out of radioactive or hazardous waste and a method of making the same | |
| JPS6332399A (en) | Processing vessel for radioactive waste, etc. and manufacture thereof | |
| US4622175A (en) | Process for solidifying radioactive waste | |
| KR102181217B1 (en) | A method of solidifying radioactive waste and the solidified waste form thereof | |
| GB2216711A (en) | Process of filling cavities | |
| JPS61245095A (en) | Waste treating vessel | |
| US5457263A (en) | Method for containing radioactive waste | |
| JP7159147B2 (en) | Solidified geopolymer manufacturing method and solidified geopolymer manufacturing system | |
| JPS62151799A (en) | Transport-treating vessel having improved shock resistance and manufacture thereof | |
| JPS61178698A (en) | Method of hardening water glass | |
| JPH073000U (en) | Treatment container for radioactive waste | |
| JP2003502623A (en) | Radioactive waste disposal | |
| EP3206210B1 (en) | Concrete container and manufacturing method thereof | |
| JPH032280B2 (en) | ||
| JPH03150499A (en) | Solidification of radioactive waste | |
| JPS61287601A (en) | Treating vessel for waste | |
| JP2993485B2 (en) | Solidification material for radioactive waste and method for solidifying radioactive waste | |
| JP2000338295A (en) | Cement material for solidifying liquid waste in reactor | |
| RU2062520C1 (en) | Method for packing radiowastes and impregnating compound for container surface treatment | |
| JPH0616389Y2 (en) | lid | |
| JP3029212B2 (en) | Radioactive waste disposal container | |
| JPS6288999A (en) | Method of solidifying and processing radioactive incombustible solid waste | |
| JPS6118601A (en) | Waste housing vessel | |
| GB2049261A (en) | Method of disposal of tritium- containing water wastes |